JPS63266395A - Fuel leakage inspection device - Google Patents
Fuel leakage inspection deviceInfo
- Publication number
- JPS63266395A JPS63266395A JP62099932A JP9993287A JPS63266395A JP S63266395 A JPS63266395 A JP S63266395A JP 62099932 A JP62099932 A JP 62099932A JP 9993287 A JP9993287 A JP 9993287A JP S63266395 A JPS63266395 A JP S63266395A
- Authority
- JP
- Japan
- Prior art keywords
- water
- inspection
- gas
- fuel leakage
- fuel
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 239000000446 fuel Substances 0.000 title claims abstract description 37
- 238000007689 inspection Methods 0.000 title abstract description 39
- 239000000498 cooling water Substances 0.000 claims abstract description 9
- 238000012360 testing method Methods 0.000 claims description 30
- 238000000746 purification Methods 0.000 claims description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 62
- 230000004992 fission Effects 0.000 abstract description 13
- 239000007788 liquid Substances 0.000 abstract description 6
- 238000005259 measurement Methods 0.000 abstract description 2
- 238000012546 transfer Methods 0.000 abstract description 2
- 238000004140 cleaning Methods 0.000 abstract 4
- 238000004868 gas analysis Methods 0.000 abstract 1
- 238000006467 substitution reaction Methods 0.000 abstract 1
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 6
- 239000004327 boric acid Substances 0.000 description 6
- 238000001514 detection method Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 239000008213 purified water Substances 0.000 description 3
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- FHNFHKCVQCLJFQ-NJFSPNSNSA-N Xenon-133 Chemical compound [133Xe] FHNFHKCVQCLJFQ-NJFSPNSNSA-N 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000012790 confirmation Methods 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000001934 delay Effects 0.000 description 1
- 238000007865 diluting Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 230000035945 sensitivity Effects 0.000 description 1
- 230000000007 visual effect Effects 0.000 description 1
- 239000002351 wastewater Substances 0.000 description 1
- 239000002023 wood Substances 0.000 description 1
- 150000003736 xenon Chemical class 0.000 description 1
- 229940106670 xenon-133 Drugs 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
［産業上の利用分野］
この発明は、検査ビット内に存する冷却材としての水の
中に設置された燃料集合体の燃料漏洩検査装置に関する
ものである。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to a fuel leakage inspection device for a fuel assembly installed in water as a coolant existing in an inspection bit.
［従来の技術］
第２図は従来の燃料漏洩検査装置の主要部の系統を示す
図で、ｌは検査ビット、２は漏洩検査装置、３はこの漏
洩検査装置２内に収納される燃料集合体、４はシツピン
グキャップ、５は冷却水の液面、６は自由液面、７はガ
ス加圧容器、８はガス分析装置、９はガスポンプ、ｌＯ
は弁である。[Prior Art] Fig. 2 is a diagram showing the system of the main parts of a conventional fuel leakage testing device, where l is an inspection bit, 2 is a leakage testing device, and 3 is a fuel assembly housed in this leakage testing device 2. 4 is a shipping cap, 5 is a cooling water level, 6 is a free liquid level, 7 is a gas pressurized container, 8 is a gas analyzer, 9 is a gas pump, 1O
is a valve.
４ｉ２図の装置において、漏洩検査は検査ビットｌ内に
設置された漏洩検査装置２によって、燃料集合体３から
漏出してくる核分裂生成ガス（例えばキセノン−１３３
）を対象として測定される。実際の手順としては、漏洩
検査装置２の可動形のシツピングキャップ４をとり外し
、燃料集合体３を漏洩検査装置２内へ収納する。その後
、再びシツピングキャップ４を正規の位置に設置し、弁
ＩＯを開き、ガス加圧容器７よりガスを加圧すると。In the apparatus shown in Fig. 4i2, leakage detection is performed using a leakage detection device 2 installed in the inspection bit l to detect fission product gas (for example, xenon-133) leaking from the fuel assembly 3.
) is measured. The actual procedure is to remove the movable shipping cap 4 of the leak testing device 2 and store the fuel assembly 3 into the leak testing device 2. Thereafter, the shipping cap 4 is placed in its proper position again, the valve IO is opened, and the gas is pressurized from the gas pressurization container 7.
シツピングキャップ内４に自由液面６か形成され、弁ｌ
Ｏを閉じることにより漏洩検査ｓｍの系統が周囲の水と
隔離され、閉ループか形成される。そこで、ガスポンプ
９を始動し、漏洩検査装置２内の水中の核分裂生成ガス
を循環ガス中へ移行させ、ガス分析装置８により連続計
測し、燃料漏洩の有無を測定する。ところが、この測定
の際、何らかの原因により、漏洩検査装置２の周囲の検
査ビット木そのものが核分裂生成ガスによって既に汚染
されている場合には、漏洩検査装置２内の水中の核分裂
生成ガスが測定され、そのため被検査燃料集合体３が健
全燃料にもかかわらず、燃料漏洩の判定が下されること
になる。このような場合には、漏洩検査そのものが実施
できないこととなり、原子力発電プラントの定期検査期
間の大幅な延長を余儀なくされると共に、検査に大きな
障害となる。A free liquid level 6 is formed in the shipping cap 4, and the valve l
By closing O, the leakage test sm system is isolated from the surrounding water and a closed loop is formed. Therefore, the gas pump 9 is started, and the nuclear fission product gas in the water in the leakage inspection device 2 is transferred into the circulating gas, and the gas is continuously measured by the gas analyzer 8 to determine whether there is a fuel leak. However, during this measurement, if the test bit tree itself around the leakage testing device 2 is already contaminated with fission gas for some reason, the fission gas in the water inside the leakage testing device 2 will not be measured. Therefore, even though the fuel assembly 3 to be inspected is a healthy fuel, it is determined that there is a fuel leak. In such a case, the leakage inspection itself cannot be carried out, which necessitates a significant extension of the periodic inspection period for the nuclear power plant and poses a major obstacle to the inspection.
そこで、検査ビット水の汚染の影響を除くためには、シ
ツピングキャップ４にガス加圧器７よりガスを加圧し、
自由液面６を形成し、隔離した後、漏洩検査装７ａ２内
の水のみをきれいな水に入換ればよいことが分かる。従
来は純水を注入しようとしたが、周囲の水は燃料集合体
の臨界防止のために硼酸が一定濃度溶解しているため、
硼酸を希釈しないようにするため、あらかじめ純水に硼
酸を溶解し、所定の濃度に調節し必ｌｉ［Ｆｋを貯蔵し
ておく必要があった。また、その注入水は１回当り約２
００愛とすると、全燃料集合体約２００体につきｗｔ量
約４０ｍ″がとなる。Therefore, in order to eliminate the influence of contamination of the test bit water, the shipping cap 4 is pressurized with gas from the gas pressurizer 7.
It can be seen that after forming and isolating the free liquid level 6, only the water in the leakage testing device 7a2 needs to be replaced with clean water. Previous attempts were made to inject pure water, but the surrounding water had a certain concentration of boric acid dissolved in it to prevent the fuel assembly from becoming critical.
In order to avoid diluting boric acid, it was necessary to dissolve boric acid in pure water in advance, adjust it to a predetermined concentration, and store Fk. In addition, the injection water is about 2
00 love, the wt amount is about 40 m'' for about 200 total fuel assemblies.
［発明が解決しようとする問題点］
上記のような従来の燃料漏洩検査装置は、純水に硼酸を
所定の濃度だけ溶解させて貯蔵したものを漏洩検査装置
内に注入するために、全燃料集合体に対して約４０ｍ″
という大９の水が検査ピットに加わることになり、さら
にその水を検査終了後、処分しなければならないという
問題が生じる。[Problems to be Solved by the Invention] In the conventional fuel leakage testing device as described above, boric acid dissolved in pure water at a predetermined concentration is stored and injected into the leakage testing device. Approximately 40m″ to the aggregate
This results in the addition of a large amount of water to the inspection pit, and the problem arises that this water must be disposed of after the inspection is completed.
この発明はかかる従来の問題点を解決するためになされ
たもので、大量の排水の処分をする必要もなく、定期の
期間内に検査を終了することのできる燃料漏洩検査装置
を提供することを目的とする。This invention was made in order to solve such conventional problems, and it is an object of the present invention to provide a fuel leakage inspection device that can complete an inspection within a regular period without the need to dispose of a large amount of wastewater. purpose.
［問題点を解決するだめの手段］
上記の目的を達成するために、この発明の燃料漏洩検査
装置は燃料漏洩検査装置内へ浄化済冷却水を供給するた
めの冷却水（ビット水）浄化装置を付加したものである
。[Means for Solving the Problems] In order to achieve the above object, the fuel leakage inspection device of the present invention includes a cooling water (bit water) purification device for supplying purified cooling water into the fuel leakage inspection device. is added.
［作用］
上記の構成を有することによって、浄化装置を用いて、
予め浄化した水（ビット水）を燃料漏洩検査装置内に供
給することにより、ビット水が核分裂生成ガスで既に汚
染されている場合でも燃料漏洩検査が可能である。[Operation] By having the above configuration, using the purification device,
By supplying pre-purified water (bit water) into the fuel leakage inspection device, fuel leakage inspection is possible even if the bit water is already contaminated with fission product gas.
［実施例］
第１図はこの発明の一実施例である燃料漏洩検査装置の
主要部の系統を示す図で、１１はビット水の浄化装置、
１２は浄化配管、１３．１４は水ポンプ、１５．１６は
配管、１７は液面であり。[Embodiment] Fig. 1 is a diagram showing a system of the main parts of a fuel leakage inspection device which is an embodiment of the present invention, and 11 is a bit water purification device;
12 is a purification pipe, 13.14 is a water pump, 15.16 is a pipe, and 17 is a liquid level.
また、第２図と同一符号は四−または相当部分を示す。Further, the same reference numerals as in FIG. 2 indicate four or equivalent parts.
第１図の装置において、燃料漏洩検査の前に予め水ポン
プ１３を用いて配（ｆ’ｌ １６より汲みトげた検査ピ
ット水そのものを、詐化装＠ｌｌ内に設置された浄化配
管１２により浄化する。従って、たとえ何らかの原因に
より、漏洩検査装置２の周囲の検査ビット水そのものが
核分裂生成ガスによって既に汚染されていても、浄化配
管１２から例えば、空気をふき込んで浄化装２１１１内
のビット水中の核分裂生成ガスを空気と共に排おし、浄
化してしまう。この浄化された水は、もともと検査ピッ
ト水であり、硼酸濃度は検査ビット水と同じてあり、か
つ余分な氷でないため排液も発生しない。In the apparatus shown in Fig. 1, the inspection pit water itself, which has been pumped up from the water pump 13 (f'l 16) in advance using the water pump 13, is purified by the purification pipe 12 installed in the fraud equipment @ll. Therefore, even if the inspection bit water itself around the leakage inspection device 2 is already contaminated with fission product gas for some reason, air can be blown from the purification pipe 12 to clean the bit water in the purification device 2111. This purified water is originally test pit water, and has the same boric acid concentration as the test pit water, and there is no excess ice, so it can be drained as well. Does not occur.
検査ビット水の浄化が行われた後、漏洩検査装置２に被
検査の燃料集合体３を挿入後、ガス加圧容器７のガスを
加圧し、漏洩検査装置２内に自由液面６を形成し１周囲
と隔離した後、浄化装置ｉｔにより前述の如く、予め浄
化した水を水ポンプ１４を始動し、配管１５から浄化水
を注入し、漏洩検査装置ｉ２内の木を置換する。この置
換のために要する時間は５分以内である。そして、漏洩
？ｔｗ１２内の水は完全に置換される必要はなく１例え
ばキセノン−ｌコ３の装置内許容濃度は３ Ｘ １０’
″６ルＣｉ／ＣＧ以下であるので、？を社内の汚染キセ
ノン濃度がｌ ｘ １０−’ｐｃｉ／ＣＧであればｈ以
下に希釈されていると確実に検査が実施できる。After the inspection bit water has been purified, the fuel assembly 3 to be inspected is inserted into the leakage inspection device 2, and then the gas in the gas pressurization container 7 is pressurized to form a free liquid level 6 in the leakage inspection device 2. After isolating it from the surroundings, the water pump 14 is started using water that has been purified in advance by the purification device it as described above, and the purified water is injected from the pipe 15 to replace the wood in the leakage testing device i2. The time required for this replacement is less than 5 minutes. And the leak? The water in tw12 does not need to be completely replaced; for example, the permissible concentration in the device for xenon-l is 3 x 10'.
If the concentration of contaminated xenon in the company is l x 10-'pci/CG, the test can be carried out reliably if it is diluted to below h.
置換が終了して後、ガスポンプ９を駆動し、従来と同様
のやり方で漏洩検査装置２内の水中の核分裂生成ガスを
循環ガス中へ移行させ、ガス分析装置８により連続計測
し、漏洩の有無を測定する。After the replacement is completed, the gas pump 9 is driven to transfer the nuclear fission product gas in the water in the leak detection device 2 into the circulating gas in the same manner as before, and the gas analyzer 8 continuously measures the gas to determine whether there is a leak. Measure.
燃料漏洩検査が終ｒした後、直ちに配管１６より水ポン
プ１３を使つて浄化１ｆｉｌｌ内に検査ビット水を補給
し、浄化配管１２により例えば空気で浄化しておき、次
の検査にそなえる。浄化配管１２には浄化が最適となる
微小な穴があけられ空気を気泡状とし、検査ビット水中
に溶解している汚染核分裂生成ガスをその気泡に移行さ
せ浄化するものである。Immediately after the fuel leakage test is completed, test bit water is supplied from the pipe 16 using the water pump 13 into the purification 1fill, and the water is purified with air, for example, through the purification pipe 12, in preparation for the next test. The purification piping 12 is provided with a minute hole for optimum purification to form air bubbles, and the contaminated nuclear fission product gas dissolved in the test bit water is transferred to the bubbles and purified.
尚、浄化装置ｔｌｌを検査ビット水中ないしは半水中下
に設置すれば、浄化９１１１１内の水による作業者への
放射線被曝を低減できる。また、適切な開放弁を取付け
ることによって水ポンプ１３を省略することも可能であ
る。Incidentally, if the purification device tll is installed under the test bit underwater or semi-underwater, it is possible to reduce the radiation exposure of the worker due to the water in the purification 91111. It is also possible to omit the water pump 13 by installing a suitable release valve.
また、漏洩検査装置２内の水が浄化済みのビット水に置
換されたか否かを判定する必要がある場合（例えば燃料
集合体３にリークがあれば、漏洩検査装置ｌｚ内の水は
置換されていたとしてもリーク燃料から放出される核分
裂生成物（ＦＰ）により汚れてしまうので）、予備試験
で予め注入する水の置換条件（注入量、流量）及び置換
効率を確認しておけばよい６例えば、原子炉外で着色水
を注入して視覚で確認するとか、高電気伝導度水な漏洩
検査装置２内に注入し、装置内部の電気伝導度を測定す
る方法とかを行えばよい。In addition, when it is necessary to determine whether the water in the leak test device 2 has been replaced with purified bit water (for example, if there is a leak in the fuel assembly 3, the water in the leak test device lz is replaced with purified bit water). (Even if it is, it will be contaminated by fission products (FP) released from leaked fuel), so it is best to check the replacement conditions (injection amount, flow rate) and replacement efficiency of the water to be injected in advance in a preliminary test6. For example, colored water may be injected outside the reactor for visual confirmation, or high electrical conductivity water may be injected into the leak testing device 2 and the electrical conductivity inside the device may be measured.
［発明の効果］
以り詳細に説明したとおり、この発明の燃料漏洩検査装
ａは、冷却水の浄化装置を具備した構成を有するので、
検査ビット水が核分裂生成ガスで汚染された場合にも、
漏洩検査を可能とし、検査期間の遅延を防止し、また、
ビット水の硼酸濃度調整の必要もなく、追加した水の排
液処理をすることもなく、さらに水を浄化するために燃
料漏洩検出感度は向上する。[Effects of the Invention] As explained in detail, the fuel leakage inspection device a of the present invention has a configuration including a cooling water purification device, so that
Even if the test bit water is contaminated with fission product gas,
Enables leakage inspection, prevents delays in the inspection period, and
There is no need to adjust the boric acid concentration of bit water, there is no need to drain the added water, and the fuel leakage detection sensitivity is improved because the water is further purified.
第１図はこの発明の一実施例である燃料漏洩検査装置の
主要部の系統を示す図、第２図は従来の燃料漏洩検査装
置の主要部の系統を示す図である。
図中。
１：検査ビット ２：漏洩検査装置
３：燃料集合体 ４：シッピングキャップ７：ガス加圧
器 ８：ガス分析装置
９：ガスポンプ １１：浄化装置
１２二浄化配管 １３，１４ ：水ポンプ代理人 弁
欅士 １）北 嵩 晴
第２図FIG. 1 is a diagram showing the system of the main parts of a fuel leakage testing device which is an embodiment of the present invention, and FIG. 2 is a diagram showing the system of the main parts of a conventional fuel leakage testing device. In the figure. 1: Inspection bit 2: Leakage inspection device 3: Fuel assembly 4: Shipping cap 7: Gas pressurizer 8: Gas analyzer 9: Gas pump 11: Purification device 12 Purification piping 13, 14: Water pump agent Benkeyakishi 1) Haru Kitatake Figure 2
Claims (1)
おいて、前記燃料漏洩検査装置内へ浄化済冷却水を供給
するための冷却水浄化装置を具備したことを特徴とする
燃料漏洩検査装置。A fuel leakage testing device for a fuel assembly installed in cooling water, comprising a cooling water purification device for supplying purified cooling water into the fuel leakage testing device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62099932A JPS63266395A (en) | 1987-04-24 | 1987-04-24 | Fuel leakage inspection device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62099932A JPS63266395A (en) | 1987-04-24 | 1987-04-24 | Fuel leakage inspection device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63266395A true JPS63266395A (en) | 1988-11-02 |
Family
ID=14260506
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62099932A Pending JPS63266395A (en) | 1987-04-24 | 1987-04-24 | Fuel leakage inspection device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63266395A (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006029930A (en) * | 2004-07-15 | 2006-02-02 | Hitachi Ltd | Out-pile shipping device and method for nuclear fuel |
| JP2014232075A (en) * | 2013-05-30 | 2014-12-11 | 原子燃料工業株式会社 | Damage determination device for nuclear fuel |
| JP2015087350A (en) * | 2013-11-01 | 2015-05-07 | 原子燃料工業株式会社 | Nuclear fuel sipping device and nuclear fuel sipping method |
| WO2015109182A3 (en) * | 2014-01-16 | 2015-10-22 | Dominion Engineering, Inc. | System and method for improving sensitivity of a sipping system |
| CN108463857A (en) * | 2015-08-14 | 2018-08-28 | 戴克特股份公司 | Device and method for leak detection in nuclear fuel assembly |
| JP2020501106A (en) * | 2016-09-30 | 2020-01-16 | ジョイント・ストック・カンパニー サイエンティフィック リサーチ アンド デザイン インスティテュート フォー エナジー テクノロジーズ アトムプロエクト | Monitoring system for liquid leaks from spent fuel pools |
| CN111354488A (en) * | 2018-12-21 | 2020-06-30 | 核动力运行研究所 | Nuclear fuel assembly vacuum off-line sipping detection device and method |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS539991A (en) * | 1976-07-14 | 1978-01-28 | Hitachi Ltd | Broken fuel detecting method |
-
1987
- 1987-04-24 JP JP62099932A patent/JPS63266395A/en active Pending
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS539991A (en) * | 1976-07-14 | 1978-01-28 | Hitachi Ltd | Broken fuel detecting method |
Cited By (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2006029930A (en) * | 2004-07-15 | 2006-02-02 | Hitachi Ltd | Out-pile shipping device and method for nuclear fuel |
| JP2014232075A (en) * | 2013-05-30 | 2014-12-11 | 原子燃料工業株式会社 | Damage determination device for nuclear fuel |
| JP2015087350A (en) * | 2013-11-01 | 2015-05-07 | 原子燃料工業株式会社 | Nuclear fuel sipping device and nuclear fuel sipping method |
| JP2017503170A (en) * | 2014-01-16 | 2017-01-26 | ドミニオン エンジニアリング, インク.Dominion Engineering, Inc. | System and method for improving the sensitivity of a shipping system |
| KR20160106727A (en) * | 2014-01-16 | 2016-09-12 | 도미니온 엔지니어링 인코포레이티드 | System and method for improving sensitivity of a sipping system |
| CN105981109A (en) * | 2014-01-16 | 2016-09-28 | 多明尼奥工程公司 | System and method for improving sensitivity of a sipping system |
| WO2015109182A3 (en) * | 2014-01-16 | 2015-10-22 | Dominion Engineering, Inc. | System and method for improving sensitivity of a sipping system |
| US20170032854A1 (en) * | 2014-01-16 | 2017-02-02 | Dominion Engineering, Inc. | System and method for improving sensitivity of a sipping system |
| US11170904B2 (en) | 2014-01-16 | 2021-11-09 | Dominion Engineering, Inc. | System and method for improving sensitivity of a sipping system |
| CN108463857A (en) * | 2015-08-14 | 2018-08-28 | 戴克特股份公司 | Device and method for leak detection in nuclear fuel assembly |
| JP2020501106A (en) * | 2016-09-30 | 2020-01-16 | ジョイント・ストック・カンパニー サイエンティフィック リサーチ アンド デザイン インスティテュート フォー エナジー テクノロジーズ アトムプロエクト | Monitoring system for liquid leaks from spent fuel pools |
| CN111354488A (en) * | 2018-12-21 | 2020-06-30 | 核动力运行研究所 | Nuclear fuel assembly vacuum off-line sipping detection device and method |
| CN111354488B (en) * | 2018-12-21 | 2022-08-19 | 核动力运行研究所 | Nuclear fuel assembly vacuum off-line sipping detection device and method |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JPS63266395A (en) | Fuel leakage inspection device | |
| CA2135501A1 (en) | Leak-detection system and method for detecting a leaking container | |
| US20090154635A1 (en) | Drainage apparatus and drainage method for reactor coolant system | |
| US3073767A (en) | Reactor fuel elements testing container | |
| CN111354488B (en) | Nuclear fuel assembly vacuum off-line sipping detection device and method | |
| US5126100A (en) | System for qualification of chemical decontamination methods for decontamination of nuclear reactor systems | |
| CN209247279U (en) | A kind of gate valve suppresses system online | |
| CN109495987B (en) | Electric heating element deformation detection control system | |
| KR200405754Y1 (en) | Apparatus for the replication of indication on the interior cladding surface of nuclear reactor | |
| GB2175374B (en) | Test method for a normally closed check valve | |
| CN203191564U (en) | Machine for automatic cleaning, inspection, and examination of radioactive source | |
| WO2003034442A1 (en) | Method and device for liquid coolant nuclear reactor fuel rod assembly handling and leakage monitoring | |
| JP3077749B2 (en) | Leakage tube identification method for heat exchanger | |
| RU1795327C (en) | Method of testing tightness of elements of fuel system with the aid of radioactive indicators | |
| JPS5928695A (en) | Failed fuel detecting device | |
| CN118258564A (en) | Nuclear power plant primary loop main pump sealing static off-line test device | |
| JPS6063496A (en) | Method of detecting damage of fuel | |
| Lindauer | PROGRAM FOR THE HRT CORE PROCESSING PLANT | |
| JPH0363719B2 (en) | ||
| JP2005106492A (en) | Method of measuring leakage amount of reactor coolant in high-temperature gas furnace | |
| JPH0473117B2 (en) | ||
| Böck et al. | Operation experience with the TRIGA reactor Vienna | |
| Bengel et al. | TMI-2 reactor vessel head removal | |
| JP2004317270A (en) | Leak spot specifying device | |
| KR820000833B1 (en) | Crack detection ceil for checking the leak prootness of fuel element units |